Effect of pedestal height and internal transport barriers on International Thermonuclear Experimental Reactor target steady state simulations

Rafiq, T; Kritz, A H; Bateman, G; Kessel, C; McCune, D C; Budny, R V

doi:10.1063/1.3660265

Title: Effect of pedestal height and internal transport barriers on International Thermonuclear Experimental Reactor target steady state simulations

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Abstract

The Tokamak simulation code (TSC) is used to provide initial conditions for predictive TRANSPort and integrated modeling code (PTRANSP) simulations of ITER target steady state scenarios. The PTRANSP simulations are carried out using the new multi-mode (MMM7.1) and the gyro-Landau-fluid (GLF23) transport models. It is found that there are circumstances under which the total fusion power decreases with increasing pedestal temperature height. When the total current (from magnetic axis to plasma edge) is fixed, an increased fraction of the current is concentrated in the pedestal region as the pedestal height is increased. As a consequence of the fixed total current, this results a smaller fraction of the current in the core plasma and, consequently, lower energy confinement. In previous simulations of ITER, in which the fusion power increased with increasing pedestal temperature height, the plasma current from the top of the pedestal to the magnetic axis was held fixed independent of the pedestal temperature. Simulations presented in this paper also indicate that improvement in fusion power production occurs when the lower hybrid current drive is replaced with electron cyclotron current drive. Again, the improvement results from the redistribution of plasma current since the lower hybrid power generally drives current closermore »« less

Authors:

Rafiq, T; Kritz, A H; Bateman, G ^[1]; Kessel, C; McCune, D C; Budny, R V ^[2]

Department of Physics, Lehigh University, 16 Memorial Drive East, Bethlehem, Pennsylvania 18015 (United States)
Princeton Plasma Physics Laboratory, Princeton University, Princeton, New Jersey 08540 (United States)

Publication Date:: Tue Nov 15 00:00:00 EST 2011

OSTI Identifier:: 22047070

Resource Type:: Journal Article

Journal Name:: Physics of Plasmas

Additional Journal Information:: Journal Volume: 18; Journal Issue: 11; Other Information: (c) 2011 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); Journal ID: ISSN 1070-664X

Country of Publication:: United States

Language:: English

Subject:: 71 CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSICS; COMPUTERIZED SIMULATION; ECR CURRENT DRIVE; ELECTRIC CURRENTS; ELECTRONS; ITER TOKAMAK; LOWER HYBRID CURRENT DRIVE; LOWER HYBRID HEATING; M CODES; PLASMA; PLASMA SIMULATION; ROTATION; SHEAR; STEADY-STATE CONDITIONS; T CODES; TRANSPORT THEORY

Citation Formats


                    Rafiq, T, Kritz, A H, Bateman, G, Kessel, C, McCune, D C, and Budny, R V. Effect of pedestal height and internal transport barriers on International Thermonuclear Experimental Reactor target steady state simulations.  United States: N. p., 2011. 
        Web.  doi:10.1063/1.3660265.

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                    Rafiq, T, Kritz, A H, Bateman, G, Kessel, C, McCune, D C, & Budny, R V. Effect of pedestal height and internal transport barriers on International Thermonuclear Experimental Reactor target steady state simulations.  United States.  https://doi.org/10.1063/1.3660265

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                    Rafiq, T, Kritz, A H, Bateman, G, Kessel, C, McCune, D C, and Budny, R V. 2011.  
        "Effect of pedestal height and internal transport barriers on International Thermonuclear Experimental Reactor target steady state simulations".  United States.  https://doi.org/10.1063/1.3660265.

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@article{osti_22047070,

  title        = {Effect of pedestal height and internal transport barriers on International Thermonuclear Experimental Reactor target steady state simulations},

  author       = {Rafiq, T and Kritz, A H and Bateman, G and Kessel, C and McCune, D C and Budny, R V},

  abstractNote = {The Tokamak simulation code (TSC) is used to provide initial conditions for predictive TRANSPort and integrated modeling code (PTRANSP) simulations of ITER target steady state scenarios. The PTRANSP simulations are carried out using the new multi-mode (MMM7.1) and the gyro-Landau-fluid (GLF23) transport models. It is found that there are circumstances under which the total fusion power decreases with increasing pedestal temperature height. When the total current (from magnetic axis to plasma edge) is fixed, an increased fraction of the current is concentrated in the pedestal region as the pedestal height is increased. As a consequence of the fixed total current, this results a smaller fraction of the current in the core plasma and, consequently, lower energy confinement. In previous simulations of ITER, in which the fusion power increased with increasing pedestal temperature height, the plasma current from the top of the pedestal to the magnetic axis was held fixed independent of the pedestal temperature. Simulations presented in this paper also indicate that improvement in fusion power production occurs when the lower hybrid current drive is replaced with electron cyclotron current drive. Again, the improvement results from the redistribution of plasma current since the lower hybrid power generally drives current closer to the plasma edge than does the electron cyclotron power. ITER simulation results obtained using the MMM7.1 transport model are compared with those using the GLF23 model. It is found that, in simulations of target steady state scenarios, momentum transport and flow-shear suppression features of the new MMM7.1 model can lead to predictions of internal transport barriers in temperature and rotation frequency.},

  doi          = {10.1063/1.3660265},

  url          = {https://www.osti.gov/biblio/22047070},
  journal      = {Physics of Plasmas},

  issn         = {1070-664X},

  number       = 11,

  volume       = 18,

  place        = {United States},

  year         = {Tue Nov 15 00:00:00 EST 2011},

  month        = {Tue Nov 15 00:00:00 EST 2011}

}

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